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| | issue date = 09/23/1988 | | | issue date = 09/23/1988 |
| | title = LER 88-018-00:on 880824,discovered That RWCU Pump Room Ambient Temp Sensor Not Installed Per Design.Caused by Lack of Installation Detail on Design Documents for Steam Leak Detection Sys.Tech Spec Change submitted.W/880923 Ltr | | | title = LER 88-018-00:on 880824,discovered That RWCU Pump Room Ambient Temp Sensor Not Installed Per Design.Caused by Lack of Installation Detail on Design Documents for Steam Leak Detection Sys.Tech Spec Change submitted.W/880923 Ltr |
| | author name = BYRAM R G, RYDER T S | | | author name = Byram R, Ryder T |
| | author affiliation = PENNSYLVANIA POWER & LIGHT CO. | | | author affiliation = PENNSYLVANIA POWER & LIGHT CO. |
| | addressee name = | | | addressee name = |
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| {{#Wiki_filter:AC~~ELZRATEDDISTRIBUTIONDEMONSTRATIONSYSTEMREGULATORYINFORMATIONDISTRIBUTIONSYSTEM(RIDS)ACCESSIONNBR:8809290378DOC.DATE:88/09/23NOTARIZED-NODOCKETFACIL:50-387SusquehannaSteamElectricStation,Unit1,Pennsylva05000387"AUTH.NAMEAUTHORAFFILIATIONRYDER,T.S.PennsylvaniaPowerSLightCo.BYRAM,R.G.PennsylvaniaPower6LightCo.RECIP.NAMERECIPIENTAFFILIATIONW/8DISTRIBUTIONCODE:IE22DCOPIESRECEIVED:LTRgENCL(SIZE:TITLE:50.73LicenseeEventReport(LER),IncidentRpt,etc.iID05000387IBNOTES:LPDR2cysTranscripts. | | {{#Wiki_filter:AC~~ELZRATED DISTRIBUTION DEMONSTRATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS) |
| | ACCESSION NBR:8809290378 DOC.DATE: 88/09/23 NOTARIZED- NO DOCKET FACIL:50-387 Susquehanna Steam Electric Station, Unit 1, Pennsylva 05000387 " |
| | AUTH. NAME AUTHOR AFFILIATION RYDER,T.S. Pennsylvania Power S Light Co. |
| | BYRAM,R.G. Pennsylvania Power 6 Light Co. |
| | RECIP.NAME RECIPIENT AFFILIATION |
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| |
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| ==SUBJECT:== | | ==SUBJECT:== |
| LER88-018-00:on880824,onechannelofRWCUsysareahightempisolationinstrumentfoundinoperable.ltr.RECIPIENTIDCODE/NAMEPD1-2LATHADANI,MINTERNAL:ACRSMICHELSONACRSWYLIEAEOD/DSP/NASAEOD/DSP/TPABDEDRONRR/DEST/CEB8HNRR/DEST/ICSB7NRR/DEST/MTB9HNRR/DEST/RSB8ENRR/DLPQ/HFB10NRR/DOEA/EAB11NRR/DREP/RPB10NUDOCS-ABSTRACTRESTELFORD,J'RES/DSIR/EIBEXTERNALEG&GWILLIAMSESHSTLOBBYWARDNRCPDRNSICMAYS,GNOTES:COPIESLTTRENCL11111111111111111111111111221111114.411111122RECIPIENTIDCODE/NAMEPD1-2PDACRSMOELLERAEOD/DOAAEOD/DSP/ROABARM/DCTS/DABNRR/DEST/ADS7ENRR/DEST/ESB8DNRR/DEST/MEB9HNRR/DEST/PSBSDNRR/DEST/SGBSDNRR/DLPQ/QAB10NRR/DREP/RAB10NRR/DRIS/SIB9AREGFILE02GNlFILE01FORDBLDGHOYIALPDRNSICHARRIS,JCOPIESLTTRENCL11221122111011111111111111111111112211ARID8ATOTALNUMBEROFCOPIESREQUIRED:LTTR49ENCL48 NRCForm388(9-83)LICENSEEEVENTREPORT(LER)US.NUCLEARREGULATORYCOMMISSIONAPPROVEDOMBNO.31604104EXPIRES:8/31/SSFACILITYNAME(IISusquehannaSteamElectricStation-Unit1DOCKETNUMBER(2IPACE305000871OF0TITLE(4)OneChannelofRWCUSystemAreaHighTemperatureIsolationInstnmantFoundInoperableEVENTDATE(5)LERNUMBER(SIREPORTDATE(7)OTHERFACILITIESINVOLVED(8)MONTHDAYYEARYEAR@StOVENTIAL8ES'UMBERINUMBERRE~MONTHOAYYEARFACILITYNAMESDOCKETNUMBER(S)05000082488880180009238805000OPERATINOMODE(9)POWERLEVEL1ppP'gA"20A02(b)20.405(e)(1)(II20.405(e)(1)(N)20.405(e)0)(ill)20AOS(s)(t)(lvl20.405(s)(tI(v)20AOS(c)5028(c)(1)50.38(c)(2)X60.73(s)(21(II50.73(e)(2)(ll)50.73(s)(2)(IB)LICENSEECONTACTFORTHISLER(12)60.73(sl(2)(lv)~60.73(e)(2l(v)60.73(e)(2)(ril)50.73(e)(2)(vill)(A)50.73(sl(2)(rillI~(8)60.73(e)(2)(s)THISREPORTISSUBMITTEDPURSUANTTOTHEREOUIREMENTSOF10CFA('It(Checkonrotmoteoltbrfolios(for)(11)73.71(b)73.71(c)OTHER(SpecifyInAbttrrctbelowendInTest,HI(CForm3EBAJNAMET.S.der-Pn)erProductionEnineerTELEPHONENUMBERAREACODE717542-235COMPLETEONELINEFOREACHCOMPONENTFAILUREDESCRIBEDINTHISREPORT(13)CAUSESYSTEMCOMPONENTMANUFAC.TURERAEPORTABLETONPADSI<<RMCAUSESYSTEMCOMPONENTMANUFAC'UREREPORTABLETONPRDSo'w.waav'.t,..,,....SUPPLEMENTALREPOATEXPECTED(14)XNOYES(IIyrs,complrtrEXPECTEDSIIB4(ISSIOHOATEIABsTRAcT(Limittolr00tpecrt,I.e.,epptoslmetrlyfi(terntlnrfreprcetypewrittenllnNI(18)EXPECTEDSU8MISSIONDATE(16)MONTHDAYYEAROnAugust24,1988,itwasdiscoveredthattheHWCUPumpRoomambienttemperaturesensor,TE-G33-1N016A,wasnotinstalledperdesign.TE-G33-1N016AwasdiscoveredtohavebeeninstalledinalocationinwhichitwouldnothavedetectedaHWCUsteamleakintheHNCUPumpRoomarea.Theinstallationerrorwasdiscoveredduringawalkdownofthesteamleakdetectionsystem.ThewalkdawnhadbeeninitiatedinresponsetorecentproblemsidentifiedontheMSLDTtriplogic.Rootcauseofthiseventwasattributedtoalackofinstallationdetailonthedesigndocumentsforthesteamleakdetectionsystem.TheventilationdrawingusedforidentificationofinstrumentlocationforTE-G33-1N016Awasvagueanddidnotclearlyshawthemountinglocation.Thisresultedinthetemperaturesensorbeinginstalledinside'themainsteamtunnelexhaustductinsteadofbeinginstalledonthewalloftheHWCUpumprocm.Theeventhasbeendeterminedtobereportableper10CFR50.73(a)(2)(i)(B),inthatonetriplogicchannelfortheHNCUPumpRoomHWCUleakdetectionambienttemperaturetriplogichasbeeninoperablepriortoAugust24,1988andwouldnothavebeenabletoperformitsdesignfunction.AnewtemperatureinstrumentwasinstalledintheproperlocationwithintheHWCUPumpRoomandtheoriginaltemperatureinstrumentwasleftasasparedeviceintheMSLexhaustduct.Ataskforceisintheprocessofreviewingtheentiresteamleakdetectionsystemforadegcacyandwillbeprovidingrecammndationsforpermanentcorrectiveaction.ThefindingsofthistaskteamwillbereportedinafollawuptoLER88-017-00(Docket50-387)andthisLERwillnotbeupdated.('S0929037SSSO3PDRADOCK05003S7IPDCNRCForm3SS(983)
| | LER 88-018-00:on 880824,one channel of RWCU sys area high temp isolation instrument found inoperable. |
| NRCForm366A(943)rLICENSEEEVENTREPORT(LER)TEXTCONTINUATIONU.S.NUCLEARREOULATORYCOMMISSIONAPPROVEOOMBNO.3150M(04EXPIRES:8/31/68FACILI'TYNAME(1)OOCKETNUMBER(2)LERNUMBER(6)YEAR%caEEQUENTIALiPSIREvlsloNCONNVMSCR(~"NVMCERPACE(3)Unit1SusehannaSteamElectricStation0500038788018-00030F03TEXT///morespace/sa/O/rarLusa///Oora/HRCForm365rE's/03)CORRECZIVEACZIONSArequestforenforcementdiscretionwassubnittedtotheNHCforrelieffranTechnicalSpecification3.3.2.TheprovisionsofthistechnicalspecificationrequireplacingthetripsysteminthetrippedconditionorclosingtheaffectedsystemisolationvalveseitherofwhichwouldhavecausedisolationofHhUJfranthereactorvesseluntiltheinoperablechannelofHNCUtemperatureisolationinstrumentationcouldberestoredtooperablestatus.HavingHNCUisolatedfranthereactorvesselfortheextendedperiodoftimeanticipatedtoreturntheinoperablechanneltooperablestatuswouldresultinsignificantdegradationofreactorcoolantchemistryandcouldeventuallyrequireshuttingtheunit.dawn.Therequestwasgrantedfortheperiodoftimeendingat,11:00a.m.onAugust29,1988.OnAugust26f1988anewtemperatureinstr(mentwasinstalledintheproperlocationwithintheHNCUPumpRoanandtheoriginaltemperatureinstrumentwasleftasasparedeviceatitslocationinthemainsteamtunnelexhaustduct.Appropriatedrawingswererevisedtoreflectthenewplantconfigurationforthesedevices.Ataskteamhadbeenpreviously-formulatedtoreviewthesubjectofsteamleakdetection.Anin-depthreview,willbeperformedforallleakdetectionsystemsincludingtheHNCU,ResidualHeatRemoval(RHR,EIISCode:BO),ReactorCoreIsolationCooling(RCIC,EIISCode:BN),HighPressureCoolantInjection(HPCI,EIISCode:BJ),andMSLLeakDetectionSystems.Calculationsanddesignbaseswillbereviewedforadequacyanddeterminationoftherootcauseandappropriatelong-termcorrectiveactionswillbeperformed.ThefindingsofthistaskteamwillbereportedinafollowuptoLER88-017-00(Docket50-387)andthisLERwillnotbeupdated.ADDITIONALINFORMATIONFailedCaagmnentIdentification:Notapplicable.PreviousSimilarEvents:NotApplicableNRCfORM366A(983)*U.S.GPO:(985&524538/455 NRCForm'3SBA(543)LICENSEEEVENTREPORT(LER)TEXTCONTINUATIONU.S,NUCLEARREGULATORYCOMMISSIONAPPROVEDOMSNO.3)50-GIGAEXPIRES:5/3)/SSFACILITYNAMEl)lDOCKETNUMBER(2)LERNUMBER(5)PAGE(3)Unit1SusquehannaSteamElectricStationTEXT//fmoroF/>>co/F/Fr/ro~/Iroo////Or>>/HRCForrrr35EA'F/07)DESCRIPTIONOFEVEÃZo5ooo387"EAR')k88SEOVENTIALNUMBERREVISIONNUMBER002OF03OnAugust24,1988,itwasdiscoveredthattheReactorWaterCleanup(HWCU,EIISCode:CE)PumpRoamambienttemperaturesensor,TE-G33-1N016A,wasnotinstalledperdesign.TE-G33-1N016AhadbeeninstalledinalocationinwhichitwouldnothavedetectedasteamleakintheHWCUPumpRoamarea.Theinstallationerrorwasdiscoveredduringawalkdownofthesteamleakdetectionsystem.ThewalkdownhadbeeninitiatedinresponsetorecentproblemsidentifiedontheMainSteamLine(MSL,EIISCode:SB)differentialtemperaturetriplogicwhichwerereportedinLER88-016-00(Docket50-387).CAUSEOFEVENTRootcauseofthiseventwasattributedtoalackofinstallationdetailonthedesigndocumentsforthesteamleakdetectionsystem.Theventilationdrawing(V-28-5)usedforidentificationofinstrumentlocationforTE-G33-1N016Awasvagueanddidnotclearlyshowthemountinglocation.Thisresultedinthete(T)peraturesensorbeinginstalledinsidethemainsteamtunnelexhaustductinsteadofbeinginstalledonthewalloftheRÃCUpumproan.REPORTABILITY/ANALYSISTheeventhadbeendeteznunedtobereportableper10CFR50.73(a)(2)(i)(B),inthatonetriplogicchannelfortheHNCUPumpRoomHNCUleakdetectionambientte(nperaturetriplogichasbeeninoperablepriortoAugust24,1988andwouldnothavebeenabletoperformitsdesignfunction.Section7.3.1a.2.4.1.9,6.10oftheFSARprovidediscussiononthevariousmethodsofleakdetectionavailabletodetectasteamleakassociatedwiththeHWCUsystem."DiversityoftripinitiationsignalsforRWCUsystemlinebreakisprovidedbyhighdifferentialflow,highflow,ambientanddifferentialtemperature,andReactorVessellow,lowwaterlevel,Level2.Anincreaseindifferentialflow,spacetaT)perature,differentialtemperature,orlowReactorVesselwaterlevelwillinitiateHWCUisolation."WithexceptionofthischannelandthepenetrationroomDTdetection,inoperablepriortoAugust5,1988asreportedinLER88-017-00(Docket50-'387),theremainingsafetysystemswereintacttodetectabreechinthereactorcoolantpressureboundaryfortheHNCU,system.TherewasnocaT)pranisetothehealthandsafetyofthepublicandnosafetyconsequencesoccurred.NRCFORMSBBA(543)oU.S.GPO:ISSSO52E535/EES PennsylvaniaPower&LightCompanyTwoNorthNinthStreet~Allentown,PA18101~21517705151September23,l988U.S.NuclearRegulatoryCarmissionDocumntControlDeskWashington,DC20555t[SUSQUKRNNASTEMEKZCTRICSTATIONLICENSEEEVENTREPORT88-018-00FILER41-2PLAS-338DocketNo.50-387LicenseNo.NPF-14AttachedisLicenseeEventReport88-018-00.Thiseventwasdeterminedreportableper10CFR50.73(a)(2)(i)(B)inthatonechanneloftheReactorWaterCleanupSystemAreaHighTemperatureisolationinstrumentationwas-foundtobeinoperableduetomislocationofatemperaturesensor.R.G.SuperinentofPlant-SusquehannaTSR/mjmcc:Mr.WilliamT.RussellRegionalAdministrator,RegionIU.S.NuclearRegulatoryCcmtission475AllendaleRoadKingofPrussia,PA19406Mr.FrankYoungSr.ResidentInspectorU.S.NuclearRegulatoryCcmtissionP.O.Box52Shickshinny,PA18655}}
| | W/8 ltr. iI DISTRIBUTION CODE: IE22D COPIES RECEIVED: LTR g ENCL ( |
| | TITLE: 50.73 Licensee Event Report (LER), Incident Rpt, etc. |
| | SIZE: |
| | D NOTES:LPDR 2 cys Transcripts. 05000387IB RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL A PD1-2 LA 1 1 PD1-2 PD 1 1 THADANI,M 1 1 INTERNAL: ACRS MICHELSON 1 1 ACRS MOELLER 2 2 ACRS WYLIE 1 1 AEOD/DOA 1 1 AEOD/DSP/NAS 1 1 AEOD/DSP/ROAB 2 2 AEOD/DS P/TPAB 1 1 ARM/DCTS/DAB 1 1 DEDRO 1 1 NRR/DEST/ADS 7E 1 0 NRR/DEST/CEB 8H 1 1 NRR/DEST/ESB 8D 1 1 NRR/DEST/ICSB 7 1 1 NRR/DEST/MEB 9H 1 1 NRR/DEST/MTB 9H 1 1 NRR/DEST/PSB SD 1 1 NRR/DEST/RSB 8E 1 1 NRR/DEST/SGB SD 1 1 NRR/DLPQ/HFB 10 1 1 NRR/DLPQ/QAB 10 1 1 NRR/DOEA/EAB 11 1 1 NRR/DREP/RAB 10 1 1 NRR/DREP/RPB 10 2 2 NRR/DRIS/SIB 9A 1 1 NUDOCS-ABSTRACT 1 1 REG FILE 02 1 1 RES TELFORD,J 1 1 1 1 |
| | 'RES/DSIR/EIB 1 1 GNl FILE 01 1 1 EXTERNAL EG&G WILLIAMSE S 4 .4 FORD BLDG HOY I A 1 1 R |
| | H ST LOBBY WARD 1 1 LPDR 2 2 NRC PDR 1 1 NSIC HARRIS,J 1 1 I NSIC MAYS,G 1 1 D |
| | NOTES: 2 2 8 |
| | A TOTAL NUMBER OF COPIES REQUIRED: LTTR 49 ENCL 48 |
| | |
| | NRC Form 388 US. NUCLEAR REGULATORY COMMISSION (9-83) |
| | APPROVED OMB NO. 31604104 EXPIRES: 8/31/SS LICENSEE EVENT REPORT (LER) |
| | FACILITYNAME (II DOCKET NUMBER (2I PACE 3 Susquehanna Steam Electric Station Unit 1 0 5 0 0 0 8 7 1 OF0 TITLE (4) |
| | I One Channel of RWCU System Area High Temperature Isolation Instnmant Found Inoperable EVENT DATE (5) LER NUMBER (SI REPORT DATE (7) OTHER FACILITIES INVOLVED (8) |
| | MONTH DAY YEAR YEAR @ StOVENTIAL |
| | 'UMBER I 8ES RE~ |
| | NUMBER MONTH OAY YEAR FACILITYNAMES DOCKET NUMBER(S) 0 5 0 0 0 0 8 2 4 8 888 0 1 8 00 092 3 88 0 5 0 0 0 THIS REPORT IS SUBMITTED PURSUANT TO THE REOUIREMENTS OF 10 CFA ('I t (Check onr ot mote ol tbr folios(for) (11) |
| | OPERATINO MODE (9) 20A02(b) 20AOS(c) 60.73(sl(2)(lv) 73.71(b) |
| | POWER 20.405(e) (1) (II 5028(c) (1) ~ |
| | 60.73(e) (2l(v) 73.71(c) |
| | (2)(rill LEVEL 1 p p 20.405(e)(1)(N) 50.38(c) (2) 60.73(e)(2)(ril) OTHER (Specify In Abttrrct below end In Test, HI(C Form P'gA" 20.405(e) 0)(ill) X 60.73(s)(21(II 50.73(e) (2)(vill)(A) 3EBAJ 20AOS(s)(t)(lvl 50.73(e)(2)(ll) 50.73 (sl (8) 20.405(s)(t I(v) 50.73(s) (2) (IB) 60.73(e) (2)(s) |
| | LICENSEE CONTACT FOR THIS LER (12) |
| | NAME TELEPHONE NUMBER AREA CODE T.S. der Pn)er Production En ineer 71 754 2 2 3 5 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13) |
| | MANUFAC. AEPORTABLE MANUFAC EPORTABLE CAUSE SYSTEM COMPONENT TO NPADS CAUSE SYSTEM COMPONENT TURER 'URER TO NPRDS o |
| | 'w |
| | .w aa v'.t, ..,,.... |
| | I<<RM SUPPLEMENTAL REPOAT EXPECTED (14) MONTH DAY YEAR EXPECTED SU 8 M I SS ION DATE (16) |
| | YES (II yrs, complrtr EXPECTED SIIB4(ISSIOH OATEI X NO ABsTRAcT (Limit to lr00 tpecrt, I.e., epptoslmetrly fi(tern tlnrfreprce typewritten llnNI (18) |
| | On August 24, 1988, it was discovered that the HWCU Pump Room ambient temperature sensor, TE-G33-1N016A, was not installed per design. TE-G33-1N016A was discovered to have been installed in a location in which detected a HWCU steam leak in the HNCU Pump Room area. The installation error it would not have was discovered during a walkdown of the steam leak detection system. The walkdawn had been initiated in response to recent problems identified on the MSL DT trip logic. Root cause of this event was attributed to a lack of installation detail on the design documents for the steam leak detection system. The ventilation drawing used for identification of instrument location for TE-G33-1N016A was vague and did not clearly shaw the mounting location. |
| | This resulted in the temperature sensor being installed inside 'the main steam tunnel exhaust duct instead of being installed on the wall of the HWCU pump rocm. The event has been determined to be reportable per 10CFR50.73(a)(2)(i)(B), in that one trip logic channel for the HNCU Pump Room HWCU leak detection ambient temperature trip logic has been inoperable prior to August 24, 1988 and would not have been able to perform its design function. A new temperature instrument was installed in the proper location within the HWCU Pump Room and the original temperature instrument was left as a spare device in the MSL exhaust duct. A task force is in the process of reviewing the entire steam leak detection system for adegcacy and will be providing recammndations for permanent corrective action. The findings of this task team will be reported in a follawup to LER 88-017-00 (Docket 50-387) and this LER will not be updated. |
| | SSO 3 ('S0929037S PDR ADOCK 050 03S7 I PDC NRC Form 3SS (983) |
| | |
| | NRC Form 366A U.S. NUCLEAR REOULATORY COMMISSION (943) r LICENSEE EVENT REPORT (LER) TEXT CONTINUATION APPROVEO OMB NO. 3150M(04 EXPIRES: 8/31/68 FACILI'TY NAME (1) OOCKET NUMBER (2) LER NUMBER (6) PACE (3) |
| | %ca EEQUENTIAL iPSI REvlsloN YEAR CON NVMSCR (~" NVMCER Unit 1 Sus ehanna Steam Electric Station 05000387 8 8 018 0 0 0 30F 0 3 TEXT ///more space /s a/O/rarL usa ///Oora/HRC Form365rE's/03) |
| | CORRECZIVE ACZIONS A request for enforcement discretion was subnitted to the NHC for relief fran Technical Specification 3.3.2. The provisions of this technical specification require placing the trip system in the tripped condition or closing the affected system isolation valves either of which would have caused isolation of HhUJ fran the reactor vessel until the inoperable channel of HNCU temperature isolation instrumentation could be restored to operable status. Having HNCU isolated fran the reactor vessel for the extended period of time anticipated to return the inoperable channel to operable status would result in significant degradation of reactor coolant chemistry and could eventually require shutting the unit. dawn. The request was granted for the period of time ending at, 11:00 a.m. on August 29, 1988. On August 26f 1988 a new temperature instr(ment was installed in the proper location within the HNCU Pump Roan and the original temperature instrument was left as a spare device at its location in the main steam tunnel exhaust duct. Appropriate drawings were revised to reflect the new plant configuration for these devices. A task team had been previously formulated to review the subject of steam leak detection. An in-depth review |
| | , will be performed for all leak detection systems including the HNCU, Residual Heat Removal (RHR, EIIS Code: BO), Reactor Core Isolation Cooling (RCIC, EIIS Code: BN), High Pressure Coolant Injection (HPCI, EIIS Code: BJ), and MSL Leak Detection Systems. Calculations and design bases will be reviewed for adequacy and determination of the root cause and appropriate long-term corrective actions will be performed. The findings of this task team will be reported in a followup to LER 88-017-00 (Docket 50-387) and this LER will not be updated. |
| | ADDITIONAL INFORMATION Failed Caagmnent Identification: Not applicable. |
| | Previous Similar Events: Not Applicable NRC fORM 366A *U.S.GPO:(985&524 538/455 (983) |
| | |
| | NRC Form'3SBA U.S, NUCLEAR REGULATORY COMMISSION (543) |
| | LICENSEE EVENT REPORT (LER) TEXT CONTINUATION APPROVED OMS NO. 3)50-GIGA EXPIRES: 5/3)/SS FACILITYNAME l)l DOCKET NUMBER (2) LER NUMBER (5) PAGE (3) |
| | "EAR ')k SEOVENTIAL NUMBER REVISION NUMBER Unit 1 Susquehanna Steam Electric Station o 5 o o o 3 8 7 8 8 0 0 2 OF 0 3 TEXT //fmoro F/>>co /F /Fr/ro ~ / Iroo ////Or>>/ HRC Forrrr 35EA'F/ 07) |
| | DESCRIPTION OF EVEÃZ On August 24, 1988, EIIS Code: CE) Pump Roam it was ambient discovered that the Reactor Water Cleanup temperature sensor, TE-G33-1N016A, (HWCU, was not installed per design. TE-G33-1N016A had been installed in a location in which it would not have detected a steam leak in the HWCU Pump Roam area. The installation error was discovered during a walkdown of the steam leak detection system. The walkdown had been initiated in response to recent problems identified on the Main Steam Line (MSL, EIIS Code: SB) differential temperature trip logic which were reported in LER 88-016-00 (Docket 50-387) . |
| | CAUSE OF EVENT Root cause of this event was attributed to a lack of installation detail on the design documents for the steam leak detection system. The ventilation drawing (V-28-5) used for identification of instrument location for TE-G33-1N016A was vague and did not clearly show the mounting location. This resulted in the te(T)perature sensor being installed inside the main steam tunnel exhaust duct instead of being installed on the wall of the RÃCU pump roan. |
| | REPORTABILITY/ANALYSIS The event had been deteznuned to be reportable per 10CFR50.73(a) (2) (i) (B), in that one trip logic channel for the HNCU Pump Room HNCU leak detection ambient te(nperature trip logic has been inoperable prior to August 24, 1988 and would not have been able to perform its design function. Section 7.3.1a.2.4.1.9, 6 |
| | .10 of the FSAR provide discussion on the various methods of leak detection available to detect a steam leak associated with the HWCU system. "Diversity of trip initiation signals for RWCU system line break is provided by high differential flow, high flow, ambient and differential temperature, and Reactor Vessel low, low water level, Level 2. An increase in differential flow, space taT)perature, differential temperature, or low Reactor Vessel water level will initiate HWCU isolation." With exception of this channel and the penetration room DT detection, inoperable prior to August 5, 1988 as reported in LER 88-017-00 (Docket 50-'387), the remaining safety systems were in tact to detect a breech in the reactor coolant pressure boundary for the HNCU,system. There was no caT)pranise to the health and safety of the public and no safety consequences occurred. |
| | NRC FORM SBBA o U.S.GPO: I SSS O 52E 535/EES (543) |
| | |
| | Pennsylvania Power & Light Company Two North Ninth Street ~ Allentown, PA 18101 ~ 21517705151 September 23, l988 U.S. Nuclear Regulatory Carmission Docum nt Control Desk Washington, DC 20555 t[ |
| | SUSQUKRNNA STEM EKZCTRIC STATION LICENSEE EVENT REPORT 88-018-00 FILE R41-2 PLAS - 338 Docket No. 50-387 License No. NPF-14 Attached is Licensee Event Report 88-018-00. This event was determined reportable per 10CFR50.73(a) (2) (i) (B) in that one channel of the Reactor Water Cleanup System Area High Temperature isolation instrumentation was- found to be inoperable due to mislocation of a temperature sensor. |
| | R.G. |
| | Superin ent of Plant Susquehanna TSR/mjm cc: Mr. William T. Russell Regional Administrator, Region I U.S. Nuclear Regulatory Ccmtission 475 Allendale Road King of Prussia, PA 19406 Mr. Frank Young Sr. Resident Inspector U.S. Nuclear Regulatory Ccmtission P.O. Box 52 Shickshinny, PA 18655}} |
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Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML18026A4931998-03-30030 March 1998
LER 97-007-01:on 971017,entry Into TS 3.0.3 Occurred to Allow Completion of Surveillance Testing of One Channel of Rbm.Caused by Failure of Components in LPRM Output to Rbm. Submitted TS Change Request to Extend LCO Action Statement
ML18026A4891997-11-17017 November 1997
LER 97-007-00:on 971017,TS 3.0.3 Entry Voluntarily Made. Caused by Inadequate Post Maint Testing Following Earlier Work Associated W/Components.Failed Components Repaired, Replaced & Testing Completed
ML18026A5961996-01-0202 January 1996
LER 95-013-00:on 951119,thermally Induced Pressure Locking of HPCI Valve Occurred Under Bonnet Pressure of 3,000-7,000 Psig.Damaged HPCI Injection Valve repaired.W/960102 Ltr
ML18017A0461995-07-0707 July 1995
LER 95-008-00:on 950609,shift Average Licensed Core Thermal Power Was Exceeded.Caused by Failed Instrumentation Drift. Repaired & Recalibrated Subject Instrumentation
ML18026A4261993-06-0909 June 1993
LER 90-007-01:on 900705,primary Power Supply to RPS a Power Distribution Panel Lost When One Electrical Protection Assembly (EPA) Breaker Tripped.Epa Logic Cards Reviewed & RPS Power Supply Will Be redesigned.W/930609 Ltr
ML18026A4231992-11-17017 November 1992
LER 92-016-00:on 920416,discovered That Existing Analysis for Two Spent Fuel Storage Pools Did Not Reflect Current Fuel Design & Plant Operation.Caused by Failure to Modify FSAR Analysis.Fsar Will Be revised.W/921117 Ltr
ML18017A0391991-07-26026 July 1991
LER 91-010-00:on 910628,RWCU Isolated on Two Occassions Due to Actuations of Steam Leak Detection Instrumentation. Caused by Design Deficiency & Elevated Ambient Penetration Room Temps.Temp Modules replaced.W/910726 Ltr
ML17227A2311991-07-23023 July 1991
LER 91-009-00:on 910624,RWCU Steam Leak Detection Instrumentation Discovered to Be Inadvertently Actuated During Routine Functional Testing.Caused by Adequate Verbal Communication.Technicians briefed.W/910723 Ltr
ML18026A5251991-07-0505 July 1991
LER 91-006-00:on 910608,unplanned Actuations of ESF Occurred.Caused by Unexpected Trip of Primary Power Supply EPA Breaker Losing Power.Breakers Reset & Full Power Operation Continued uninterupted.W/910705 Ltr
ML20011F7881990-03-0202 March 1990
LER 90-005-00:on 900203,station Alert Declared When Reactor Coolant Temp Exceeded 200 F Due to Temporary Loss of Normal Method Dhr.Caused by Short Circuit to Ground in Bus Distribution Panel.Circuit Breakers replaced.W/900302 Ltr
ML20005F3401990-01-0404 January 1990
LER 89-010-01:on 890920,determined That Estimated Leakage for Main Steam Line Containment Penetrations a & B Exceeded Tech Spec Limit During Local Leak Rate Testing.Cause Not Determined.Msiv Poppet Seats & Discs lapped.W/900104 Ltr
ML18040A9121988-09-23023 September 1988
LER 88-018-00:on 880824,discovered That RWCU Pump Room Ambient Temp Sensor Not Installed Per Design.Caused by Lack of Installation Detail on Design Documents for Steam Leak Detection Sys.Tech Spec Change submitted.W/880923 Ltr
ML19310G9421986-04-21021 April 1986
LER 86-005-00:on 860321 Differential Pressure Condition Detected,Causing Supply Dampers to Oscillate.Caused by Open Plenum Door & Exhaust Damper Linkage Binding.Linkage Reworked & lubricated.W/860421 Ltr
ML20024E8021983-08-19019 August 1983
LER 83-107/01P-0:on 830819,during Maint,Emergency Svc Water Loop Discharge a to Spray Pond Valve Would Travel Only in Closed Direction.Cause Unstated.Mechanical Stops Loosened, Permitting Valve to Be Opened to Proper Position
ML20024E6311983-08-0404 August 1983
Updated LER 83-093/01X-1:on 830711,31-day Functional Test of Containment Radiation Monitor a Not Performed for 830612-0711.Caused by Lack of Timely Chemistry Mgt Review of surveillance.W/830804 Ltr
ML20024D9141983-07-26026 July 1983
Updated LER 83-035/03X-1:on 830228,during 4 H RCS Unidentified Leakage Test,Pump B of Drywell Sump a Continued to Operate for 4 H W/O Change in Sump Level.Caused by Clogged Pump Impeller.Pump cleaned.W/830726 Ltr
ML20024E1601983-07-25025 July 1983
LER 83-098/03L-0:on 830625,position of Valve Indeterminate Due to Dual Status Indication for Suppression pool-to- Drywell Vacuum Breaker.Caused by Insufficient Limit Switch Plunger Position.Limit Switches adjusted.W/830725 Ltr
ML20024D9911983-07-22022 July 1983
LER 83-096/03L-0:on 830624,RCIC Leak Detection B Power Failure Alarm Received.Undervoltage Trip Caused by Loss of Startup Transformer.Inverter Manually reset.W/830722 Ltr
ML20024C2381983-06-29029 June 1983
LER 83-088/03L-0:on 830530,RCIC Pump Discharge Valve Would Not Open.Caused by Gap Between Breaker Male & Female Stab Clips.Female Clips Reworked to Allow Proper Contact. W/830629 Ltr
ML20024C1001983-06-24024 June 1983
LER 83-085/03L-0:on 830525,containment Isolation Valve for Containment Atmosphere Control Sample Line Failed to Close. Cause Not Stated.Maint Personnel Verified Switch Positioning & Reconnected circuitry.W/830624 Ltr
ML20024C1141983-06-24024 June 1983
LER 83-087/03L-0:on 830527,A Containment H2/02 Analyzers Found to Have Erratic Readings.Caused by Pressure Control Valve & Sample Pump Degradation to Point Where Proper Flow Not Maintained.Failed Components replaced.W/830624 Ltr
ML20024C2451983-06-24024 June 1983
LER 83-086/03L-0:on 830525,reactor Bldg Door Opened While Maint Performed on Turbine Bldg Side of Air Lock to Reactor Bldg.Caused by Personnel Error.Individual W/Radio Communication Will Be posted.W/830624 Ltr
ML20024C2461983-06-23023 June 1983
LER 83-084/03L-0:on 830524,during Surveillance Testing, Control Room Emergency Outside Air Supply Sys Fan Tripped. Caused by Out of Tolerance of Time Delay Relay for Heater Differential Temp.Relay reset.W/830623 Ltr
ML20024A8401983-06-21021 June 1983
LER 83-082/01T-0:on 830607,main Turbine Trip on High Reactor Pressure Vessel Level Bypassed to Clear Interlock.After Outage,Bypass Discovered Still Installed.Caused by Lack of Clear Requirement for Bypass review.W/830621 Ltr
ML20024A5331983-05-27027 May 1983
LER 83-067/01T-0:on 830516,reactor Mode Switch Placed in Startup Position & Half Scram Developed.Caused by Improper Functioning of Reactor Mode Switch Contacts.Switch Replaced. W/830527 Ltr
ML20024A3421983-05-27027 May 1983
LER 83-070/01T-0:on 830517,flow Rates Required to Maintain Positive Pressure in Control Structure Appeared to Exceed Tech Spec Limits.Flow Limit Inadvertently Omitted from Procedure.Procedure corrected.W/830527 Ltr
ML20024A3301983-05-27027 May 1983
LER 83-075/01T-0:on 830515,found Chlorine Detectors on Control Room Emergency Outside Air Supply May Prevent Operation in Pressurization Mode Following Loss of Power. Emergency Operation Procedures revised.W/830527 Ltr
ML20024A3951983-05-26026 May 1983
LER 83-071/03L-0:on 830426,overvoltage Setting on One RPS Alternate Electrical Protection Assembly Found Greater than Tech Spec Limit.Caused by Instrument Drift.Overvoltage Setting Calibr within limits.W/830526 Ltr
ML20023D5121983-05-11011 May 1983
LER 83-063/03L-0:on 830411,main Steam Line Drain Valve Leakage Exceeded Tech Spec Limit.Cause Not Stated.Seal Ring Replaced,Outboard Valve Lapped & Valves Reassembled
ML20023B8381983-04-29029 April 1983
LER 83-057/01P-0:confirms 830428 Telcon Re Incident Concerning Bypass Leakage Calculations for Feedwater Following DBA LOCA
ML20028D6871983-01-10010 January 1983
LER 83-001/01P-0:confirms 830107 Telcon Re Failure to Comply W/Action Statement Requiring Grab Samples of Offgas Sys After Declaring One Train of Hydrogen Monitor Inoperable. Caused by Inadequate Shift Turnover in Chemistry Dept
ML20028D3141983-01-0707 January 1983
LER 82-072/03L-0:on 821210,while Performing Surveillance, One Control Rod Would Not Indicate at One Position.Possibly Caused by Intermittent Fault on Circuit Board.Printed Circuit Board Reinstalled
ML20028D2871983-01-0606 January 1983
LER 82-069/03L-0:on 821207,during Startup Testing,Hpci Sys Declared Operable Prior to Closing Out Open Equipment Release Form.Caused by Work Program Design Weakness.Present Work Practice Modified
ML20028D2601983-01-0505 January 1983
LER 82-061/01T-0:on 821228,during Startup Testing,While Performing Loss of Offsite Power Test,Emergency Svc Water Pumps B & D Failed to Start.Loop B Failure Caused by Loose Relay Terminal Wiring.Loop D Caused by Contact Adjustment
ML20028D2671983-01-0505 January 1983
LER 82-062/01T-0:on 821222,during Loss of Offsite Power Startup Test,Standby Gas Treatment Sys Did Not Operate as Designed When False High Radiation Signal Received from Discharge Monitor.Caused by Monitor Failing High
ML20028B7201982-11-24024 November 1982
LER 82-045/03L-0:on 821025,essential Svc Water Pump Failed to Start.Cause Could Not Be Determined or Reproduced.Svc Pump Tested 5 Times W/O Recurrence of Failure
ML20028B5821982-11-19019 November 1982
Revised LER 82-026/01T-1:on 820717,review Revealed Certain Cables Discussed in Deficiency Rept 80-00-28 Not Flexed or Grounded Prior to Fuel Load.Caused by Failure to Maintain Control Over Fddr KRI-607 During Turnover of Const
ML20028B0301982-11-18018 November 1982
LER 82-042/01T-0:on 821117,personnel Failed to Take Grab Samples When RHR Svc Water Sys Radiation Monitor Was Inoperable
ML20028B4351982-11-18018 November 1982
LER 82-043/01T-0:on 821117,determined That Failure of Single Component Could Defeat Overload Detection & Protection Devices for Containment Penetration Carrying Power Cables for Reactor Recirculation Pumps.Cause Not Stated
ML20028A9541982-11-16016 November 1982
LER 82-040/03L-0:on 821018,deluge Sys in CREOASS Initiated. Caused by Maint Personnel Bumping Fire Sys thermo-switch on Charcoal Beds.Charcoal Changed Out & Preventive Maint Procedures Modified to Valve Out Deluge Sys During Maint
ML20028B0461982-11-12012 November 1982
Revised LER 82-003/01T-2:on 820811,during Initial Fuel Loading,Sprinkler Sys Did Not Exist in Area Designated by Tech Specs & Fire Protection Review Rept.Caused by Discrepancies in as-built Conditions.Mods Initiated
ML20028A3341982-11-0303 November 1982
LER 82-034/03L-0:on 821011,during Startup Testing,Creoass Train a Declared Inoperable When Outside Air Damper Failed to Close.Caused by Inadequate Lubrication of Actuator Stem. Stem Lubricated & Damper Returned to Svc
ML20027D0591982-10-19019 October 1982
LER 82-027/03L-0:on 820920,two Drywell/Suppression Chamber Vacuum Breakers Gave False Position Indications During Stroking.Caused by Loose Couplings Connecting Limit Switch to Vacuum Relief Valve Shaft.Set Screw Replaced
ML17139B0311982-09-13013 September 1982
LER 82-013/03L-0:on 820814,radiation Monitor Found Inoperable.Caused by Faulty Gm Tube & Signal Conditioner (Sensor Converter).Tube & Signal Conditioner Replaced & Monitor Returned to Svc
ML20027B0571982-09-0808 September 1982
LER 82-007/01T-1:on 820825,updated Secondary Containment Vol Calculation Had Not Replaced Preliminary Analysis Utilized to Obtain Values in Fsar.Vol Based on Preliminary Calculation Which Did Not Account for Floors & Equipment
ML20027A9581982-09-0303 September 1982
LER 82-005/01T-1:on 820820,during Preoperational Testing, Control Room Emergency Outside Air Supply Sys Did Not Automatically Start on Isolation Signal.Caused by Unauthorized Personnel Changing Flow Controller Switch
ML17139A9071982-08-0202 August 1982
LER 82-001/01T-0:on 820718,unacceptable Linear Indications Found by Radiograph of A-11 Weld.Cause Not Determined.Welds Repaired Per Approved Repair Program
1998-03-30
[Table view]
Category:RO)
MONTHYEARML18026A4931998-03-30030 March 1998
LER 97-007-01:on 971017,entry Into TS 3.0.3 Occurred to Allow Completion of Surveillance Testing of One Channel of Rbm.Caused by Failure of Components in LPRM Output to Rbm. Submitted TS Change Request to Extend LCO Action Statement
ML18026A4891997-11-17017 November 1997
LER 97-007-00:on 971017,TS 3.0.3 Entry Voluntarily Made. Caused by Inadequate Post Maint Testing Following Earlier Work Associated W/Components.Failed Components Repaired, Replaced & Testing Completed
ML18026A5961996-01-0202 January 1996
LER 95-013-00:on 951119,thermally Induced Pressure Locking of HPCI Valve Occurred Under Bonnet Pressure of 3,000-7,000 Psig.Damaged HPCI Injection Valve repaired.W/960102 Ltr
ML18017A0461995-07-0707 July 1995
LER 95-008-00:on 950609,shift Average Licensed Core Thermal Power Was Exceeded.Caused by Failed Instrumentation Drift. Repaired & Recalibrated Subject Instrumentation
ML18026A4261993-06-0909 June 1993
LER 90-007-01:on 900705,primary Power Supply to RPS a Power Distribution Panel Lost When One Electrical Protection Assembly (EPA) Breaker Tripped.Epa Logic Cards Reviewed & RPS Power Supply Will Be redesigned.W/930609 Ltr
ML18026A4231992-11-17017 November 1992
LER 92-016-00:on 920416,discovered That Existing Analysis for Two Spent Fuel Storage Pools Did Not Reflect Current Fuel Design & Plant Operation.Caused by Failure to Modify FSAR Analysis.Fsar Will Be revised.W/921117 Ltr
ML18017A0391991-07-26026 July 1991
LER 91-010-00:on 910628,RWCU Isolated on Two Occassions Due to Actuations of Steam Leak Detection Instrumentation. Caused by Design Deficiency & Elevated Ambient Penetration Room Temps.Temp Modules replaced.W/910726 Ltr
ML17227A2311991-07-23023 July 1991
LER 91-009-00:on 910624,RWCU Steam Leak Detection Instrumentation Discovered to Be Inadvertently Actuated During Routine Functional Testing.Caused by Adequate Verbal Communication.Technicians briefed.W/910723 Ltr
ML18026A5251991-07-0505 July 1991
LER 91-006-00:on 910608,unplanned Actuations of ESF Occurred.Caused by Unexpected Trip of Primary Power Supply EPA Breaker Losing Power.Breakers Reset & Full Power Operation Continued uninterupted.W/910705 Ltr
ML20011F7881990-03-0202 March 1990
LER 90-005-00:on 900203,station Alert Declared When Reactor Coolant Temp Exceeded 200 F Due to Temporary Loss of Normal Method Dhr.Caused by Short Circuit to Ground in Bus Distribution Panel.Circuit Breakers replaced.W/900302 Ltr
ML20005F3401990-01-0404 January 1990
LER 89-010-01:on 890920,determined That Estimated Leakage for Main Steam Line Containment Penetrations a & B Exceeded Tech Spec Limit During Local Leak Rate Testing.Cause Not Determined.Msiv Poppet Seats & Discs lapped.W/900104 Ltr
ML18040A9121988-09-23023 September 1988
LER 88-018-00:on 880824,discovered That RWCU Pump Room Ambient Temp Sensor Not Installed Per Design.Caused by Lack of Installation Detail on Design Documents for Steam Leak Detection Sys.Tech Spec Change submitted.W/880923 Ltr
ML19310G9421986-04-21021 April 1986
LER 86-005-00:on 860321 Differential Pressure Condition Detected,Causing Supply Dampers to Oscillate.Caused by Open Plenum Door & Exhaust Damper Linkage Binding.Linkage Reworked & lubricated.W/860421 Ltr
ML20024E8021983-08-19019 August 1983
LER 83-107/01P-0:on 830819,during Maint,Emergency Svc Water Loop Discharge a to Spray Pond Valve Would Travel Only in Closed Direction.Cause Unstated.Mechanical Stops Loosened, Permitting Valve to Be Opened to Proper Position
ML20024E6311983-08-0404 August 1983
Updated LER 83-093/01X-1:on 830711,31-day Functional Test of Containment Radiation Monitor a Not Performed for 830612-0711.Caused by Lack of Timely Chemistry Mgt Review of surveillance.W/830804 Ltr
ML20024D9141983-07-26026 July 1983
Updated LER 83-035/03X-1:on 830228,during 4 H RCS Unidentified Leakage Test,Pump B of Drywell Sump a Continued to Operate for 4 H W/O Change in Sump Level.Caused by Clogged Pump Impeller.Pump cleaned.W/830726 Ltr
ML20024E1601983-07-25025 July 1983
LER 83-098/03L-0:on 830625,position of Valve Indeterminate Due to Dual Status Indication for Suppression pool-to- Drywell Vacuum Breaker.Caused by Insufficient Limit Switch Plunger Position.Limit Switches adjusted.W/830725 Ltr
ML20024D9911983-07-22022 July 1983
LER 83-096/03L-0:on 830624,RCIC Leak Detection B Power Failure Alarm Received.Undervoltage Trip Caused by Loss of Startup Transformer.Inverter Manually reset.W/830722 Ltr
ML20024C2381983-06-29029 June 1983
LER 83-088/03L-0:on 830530,RCIC Pump Discharge Valve Would Not Open.Caused by Gap Between Breaker Male & Female Stab Clips.Female Clips Reworked to Allow Proper Contact. W/830629 Ltr
ML20024C1001983-06-24024 June 1983
LER 83-085/03L-0:on 830525,containment Isolation Valve for Containment Atmosphere Control Sample Line Failed to Close. Cause Not Stated.Maint Personnel Verified Switch Positioning & Reconnected circuitry.W/830624 Ltr
ML20024C1141983-06-24024 June 1983
LER 83-087/03L-0:on 830527,A Containment H2/02 Analyzers Found to Have Erratic Readings.Caused by Pressure Control Valve & Sample Pump Degradation to Point Where Proper Flow Not Maintained.Failed Components replaced.W/830624 Ltr
ML20024C2451983-06-24024 June 1983
LER 83-086/03L-0:on 830525,reactor Bldg Door Opened While Maint Performed on Turbine Bldg Side of Air Lock to Reactor Bldg.Caused by Personnel Error.Individual W/Radio Communication Will Be posted.W/830624 Ltr
ML20024C2461983-06-23023 June 1983
LER 83-084/03L-0:on 830524,during Surveillance Testing, Control Room Emergency Outside Air Supply Sys Fan Tripped. Caused by Out of Tolerance of Time Delay Relay for Heater Differential Temp.Relay reset.W/830623 Ltr
ML20024A8401983-06-21021 June 1983
LER 83-082/01T-0:on 830607,main Turbine Trip on High Reactor Pressure Vessel Level Bypassed to Clear Interlock.After Outage,Bypass Discovered Still Installed.Caused by Lack of Clear Requirement for Bypass review.W/830621 Ltr
ML20024A5331983-05-27027 May 1983
LER 83-067/01T-0:on 830516,reactor Mode Switch Placed in Startup Position & Half Scram Developed.Caused by Improper Functioning of Reactor Mode Switch Contacts.Switch Replaced. W/830527 Ltr
ML20024A3421983-05-27027 May 1983
LER 83-070/01T-0:on 830517,flow Rates Required to Maintain Positive Pressure in Control Structure Appeared to Exceed Tech Spec Limits.Flow Limit Inadvertently Omitted from Procedure.Procedure corrected.W/830527 Ltr
ML20024A3301983-05-27027 May 1983
LER 83-075/01T-0:on 830515,found Chlorine Detectors on Control Room Emergency Outside Air Supply May Prevent Operation in Pressurization Mode Following Loss of Power. Emergency Operation Procedures revised.W/830527 Ltr
ML20024A3951983-05-26026 May 1983
LER 83-071/03L-0:on 830426,overvoltage Setting on One RPS Alternate Electrical Protection Assembly Found Greater than Tech Spec Limit.Caused by Instrument Drift.Overvoltage Setting Calibr within limits.W/830526 Ltr
ML20023D5121983-05-11011 May 1983
LER 83-063/03L-0:on 830411,main Steam Line Drain Valve Leakage Exceeded Tech Spec Limit.Cause Not Stated.Seal Ring Replaced,Outboard Valve Lapped & Valves Reassembled
ML20023B8381983-04-29029 April 1983
LER 83-057/01P-0:confirms 830428 Telcon Re Incident Concerning Bypass Leakage Calculations for Feedwater Following DBA LOCA
ML20028D6871983-01-10010 January 1983
LER 83-001/01P-0:confirms 830107 Telcon Re Failure to Comply W/Action Statement Requiring Grab Samples of Offgas Sys After Declaring One Train of Hydrogen Monitor Inoperable. Caused by Inadequate Shift Turnover in Chemistry Dept
ML20028D3141983-01-0707 January 1983
LER 82-072/03L-0:on 821210,while Performing Surveillance, One Control Rod Would Not Indicate at One Position.Possibly Caused by Intermittent Fault on Circuit Board.Printed Circuit Board Reinstalled
ML20028D2871983-01-0606 January 1983
LER 82-069/03L-0:on 821207,during Startup Testing,Hpci Sys Declared Operable Prior to Closing Out Open Equipment Release Form.Caused by Work Program Design Weakness.Present Work Practice Modified
ML20028D2601983-01-0505 January 1983
LER 82-061/01T-0:on 821228,during Startup Testing,While Performing Loss of Offsite Power Test,Emergency Svc Water Pumps B & D Failed to Start.Loop B Failure Caused by Loose Relay Terminal Wiring.Loop D Caused by Contact Adjustment
ML20028D2671983-01-0505 January 1983
LER 82-062/01T-0:on 821222,during Loss of Offsite Power Startup Test,Standby Gas Treatment Sys Did Not Operate as Designed When False High Radiation Signal Received from Discharge Monitor.Caused by Monitor Failing High
ML20028B7201982-11-24024 November 1982
LER 82-045/03L-0:on 821025,essential Svc Water Pump Failed to Start.Cause Could Not Be Determined or Reproduced.Svc Pump Tested 5 Times W/O Recurrence of Failure
ML20028B5821982-11-19019 November 1982
Revised LER 82-026/01T-1:on 820717,review Revealed Certain Cables Discussed in Deficiency Rept 80-00-28 Not Flexed or Grounded Prior to Fuel Load.Caused by Failure to Maintain Control Over Fddr KRI-607 During Turnover of Const
ML20028B0301982-11-18018 November 1982
LER 82-042/01T-0:on 821117,personnel Failed to Take Grab Samples When RHR Svc Water Sys Radiation Monitor Was Inoperable
ML20028B4351982-11-18018 November 1982
LER 82-043/01T-0:on 821117,determined That Failure of Single Component Could Defeat Overload Detection & Protection Devices for Containment Penetration Carrying Power Cables for Reactor Recirculation Pumps.Cause Not Stated
ML20028A9541982-11-16016 November 1982
LER 82-040/03L-0:on 821018,deluge Sys in CREOASS Initiated. Caused by Maint Personnel Bumping Fire Sys thermo-switch on Charcoal Beds.Charcoal Changed Out & Preventive Maint Procedures Modified to Valve Out Deluge Sys During Maint
ML20028B0461982-11-12012 November 1982
Revised LER 82-003/01T-2:on 820811,during Initial Fuel Loading,Sprinkler Sys Did Not Exist in Area Designated by Tech Specs & Fire Protection Review Rept.Caused by Discrepancies in as-built Conditions.Mods Initiated
ML20028A3341982-11-0303 November 1982
LER 82-034/03L-0:on 821011,during Startup Testing,Creoass Train a Declared Inoperable When Outside Air Damper Failed to Close.Caused by Inadequate Lubrication of Actuator Stem. Stem Lubricated & Damper Returned to Svc
ML20027D0591982-10-19019 October 1982
LER 82-027/03L-0:on 820920,two Drywell/Suppression Chamber Vacuum Breakers Gave False Position Indications During Stroking.Caused by Loose Couplings Connecting Limit Switch to Vacuum Relief Valve Shaft.Set Screw Replaced
ML17139B0311982-09-13013 September 1982
LER 82-013/03L-0:on 820814,radiation Monitor Found Inoperable.Caused by Faulty Gm Tube & Signal Conditioner (Sensor Converter).Tube & Signal Conditioner Replaced & Monitor Returned to Svc
ML20027B0571982-09-0808 September 1982
LER 82-007/01T-1:on 820825,updated Secondary Containment Vol Calculation Had Not Replaced Preliminary Analysis Utilized to Obtain Values in Fsar.Vol Based on Preliminary Calculation Which Did Not Account for Floors & Equipment
ML20027A9581982-09-0303 September 1982
LER 82-005/01T-1:on 820820,during Preoperational Testing, Control Room Emergency Outside Air Supply Sys Did Not Automatically Start on Isolation Signal.Caused by Unauthorized Personnel Changing Flow Controller Switch
ML17139A9071982-08-0202 August 1982
LER 82-001/01T-0:on 820718,unacceptable Linear Indications Found by Radiograph of A-11 Weld.Cause Not Determined.Welds Repaired Per Approved Repair Program
1998-03-30
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML20217A9931999-09-30030 September 1999
NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data
ML17146B1741999-08-0303 August 1999
GL 96-06 Risk Assessment for Sses.
ML20206D3331999-04-27027 April 1999
SER of Individual Plant Examination of External Events Submittal on Susquehanna Steam Electric Station,Units 1 & 2. Staff Notes That Licensee IPEEE Complete with Regard to Info Requested by Suppl 4 to GL 88-20
ML20195B2381999-03-31031 March 1999
Redacted Version for 10CFR2.790 Request for Decommissioning Status Rept for Sses,Units 1 & 2
ML17164A8451998-10-31031 October 1998
SSES Unit 1 Tenth Refueling & Insp Outage ISI Outage Summary Rept.
ML20236N6751998-07-0909 July 1998
Part 21 & Deficiency Rept Re Notification of Potential Safety Hazard from Breakage of Cast Iron Suction Heads in Apkd Type Pumps.Caused by Migration of Suction Head Journal Sleeve Along Lower End of Pump Shaft.Will Inspect Pumps
ML20217Q4891998-04-21021 April 1998
Rev 1 to Draft LDCN 2482, FSAR Chapter 13.4 & FSAR Chapter 17.2 Changes to Support ITS Implementation
ML18026A4931998-03-30030 March 1998
LER 97-007-01:on 971017,entry Into TS 3.0.3 Occurred to Allow Completion of Surveillance Testing of One Channel of Rbm.Caused by Failure of Components in LPRM Output to Rbm. Submitted TS Change Request to Extend LCO Action Statement
ML18026A5401998-02-28028 February 1998
Monthly Operating Repts for Feb 1998 for Susquehanna Steam Electric Station.W/980313 Ltr
ML18026A4891997-11-17017 November 1997
LER 97-007-00:on 971017,TS 3.0.3 Entry Voluntarily Made. Caused by Inadequate Post Maint Testing Following Earlier Work Associated W/Components.Failed Components Repaired, Replaced & Testing Completed
ML18017A2921997-10-28028 October 1997
1997 Nrc/Fema Observed Exercise.
ML17158C1861997-06-0505 June 1997
Proceedings of Intl Topical Meeting on Advanced Reactors Safety Vol II, on 970601-05
ML20140A9661997-05-29029 May 1997
Part 21 Rept Re Ksv Emergency Diesel Generator Power Piston Failure.Caused by Jacket Water in Combustion Chamber. Recommends That Users Verify That Crown Thickness at Valve Cutout Be 100 Minimum
ML18026A4781997-03-28028 March 1997
Rev 1 to Application of Anfb to ATRIUM-10 for Susquehanna Reloads.
ML20137G6261997-03-25025 March 1997
Svcs Part 21 Rept Re Emergency Generators Installed at Zion Station Which Developed Significant Drop in Crankcase Lube Oil Level.Caused by Crack in Liner Wall,Allowing Jacket Water to Enter Chamber
ML20155F7661996-07-25025 July 1996
Partially Deleted Job Number 739619-96, Investigation of E Diesel Breaker Misalignment
ML20155F7491996-07-24024 July 1996
Independent Safety Evaluation Svcs Project Rept 3-96, Investigation of E Diesel Generator In-Operability Event
ML20117G4641996-05-14014 May 1996
Part 21 Rept Re Cooper Bessemer Reciprocating Products,Div of Cooper Cameron Corp,Issued Ltr to Define Utils/Plants Containing Similar Equipment as Supplied on Cooper Bessemer Ksv & Enterprise Dsr EDGs
ML18026A5961996-01-0202 January 1996
LER 95-013-00:on 951119,thermally Induced Pressure Locking of HPCI Valve Occurred Under Bonnet Pressure of 3,000-7,000 Psig.Damaged HPCI Injection Valve repaired.W/960102 Ltr
ML18017A0511995-11-30030 November 1995
Monthly Operating Repts for Nov 1995 for SSES Units 1 & 2. W/951215 Ltr
ML20092H7641995-08-31031 August 1995
Monthly Operating Repts for Aug 1995 for Susquehanna Ses
ML17158A8771995-08-15015 August 1995
Exercise Manual.
ML17158A8061995-07-14014 July 1995
Books 1 & 2 of ISI Outage Summary Rept SSES Unit 1 8th Refuel Outage.
ML18017A0461995-07-0707 July 1995
LER 95-008-00:on 950609,shift Average Licensed Core Thermal Power Was Exceeded.Caused by Failed Instrumentation Drift. Repaired & Recalibrated Subject Instrumentation
ML17164A6631995-04-11011 April 1995
Impact of Extending T-10 AOT from 3 to 7 Days.
ML17164A5871995-01-31031 January 1995
Monthly Operating Repts for Jan 1995 for Susquehanna Ses
ML18026A5351994-10-31031 October 1994
SSES Unit 1 & 2 MSIV Leakage Alternate Treatment Method Seismic Evaluation. W/One Oversize Drawing
ML17158A4821994-08-23023 August 1994
ISI Outage Summary Rept Unit 2 6th Refueling Outage, Books 1 & 2 of 2
ML17158A2391994-04-0505 April 1994
Books 1 & 2 of SSES Unit 1 Seventh Refueling & Insp Outage ISI Outage Summary Rept.
ML18017A2701993-12-31031 December 1993
PP&L Annual Rept 1993.
ML17158A2651993-12-31031 December 1993
Allegheny Electric Cooperative,Inc Annual Rept 1993.
ML17158A1631993-12-0909 December 1993
Remote Indication of Spent Fuel Pool Level & Temperature.
ML18026A4281993-08-16016 August 1993
PP&L Response to NRC Concerns Re Loss of Spent Fuel Pool Cooling Following Loca,Sses,Units 1 & 2.
ML18026A4261993-06-0909 June 1993
LER 90-007-01:on 900705,primary Power Supply to RPS a Power Distribution Panel Lost When One Electrical Protection Assembly (EPA) Breaker Tripped.Epa Logic Cards Reviewed & RPS Power Supply Will Be redesigned.W/930609 Ltr
ML17157C2441993-02-28028 February 1993
Monthly Operating Rept for Feb 1993 for Susquehanna Steam Electric Station,Units 1 & 2
ML18017A2031993-02-0101 February 1993
Books 1 & 2 of Unit 2 Fifth Refueling & Insp Outage,Isi Outage Summary Rept.
ML20044C2741993-01-31031 January 1993
Corrected Monthly Operating Rept for Jan 1993 for Susquehanna Steam Electric Station,Unit 2,consisting of Info on Unit Shutdowns & Power Reductions
ML17157C3691992-12-31031 December 1992
PP&L Annual Rept 1992.
ML20056C3941992-12-31031 December 1992
Allegheny Electric Cooperative,Inc Annual Rept 1992
ML18017A0421992-12-14014 December 1992
Suppl to 921127 Part 21 Rept Re High Air Concentration in Reactor Bldg Making Area Uninhabitable for Retrieving Air Filters,Per NUREG-0737,Item II.F.1.Util Current Position Re Fuel Pool Cooling Issues Contrary to Reg Guide 1.3
ML18026A2481992-11-27027 November 1992
Part 21 Rept Re Substantial Safety Hazard in Design of Facility for Loss of Normal Spent Fuel Pool Cooling
ML18026A4231992-11-17017 November 1992
LER 92-016-00:on 920416,discovered That Existing Analysis for Two Spent Fuel Storage Pools Did Not Reflect Current Fuel Design & Plant Operation.Caused by Failure to Modify FSAR Analysis.Fsar Will Be revised.W/921117 Ltr
ML17157C1421992-10-21021 October 1992
Engineering Assessment of Fuel Pool Cooling Piping EDR-G20020.
ML17157C1411992-08-31031 August 1992
Loss of Fuel Pool Cooling Event Evaluation.
ML17157C1401992-08-31031 August 1992
Review of Fuel Pool Cooling During Postulated Off-Normal & Accident Events SSES Units 1 & 2.
ML20082C4941992-08-14014 August 1992
Evaluation of Unit 1 & Unit 2 Derating of Power Cables in Raceways Wrapped W/Thermo-Lag Matl
ML17157C1381992-07-27027 July 1992
Safety Consequences of Boiling Spent Fuel Pool at Susquehanna Steam Electric Station.
ML17157B9331992-07-24024 July 1992
Sixth Refueling & Insp Outage Inservice Insp Outage Summary Rept, Books 1 & 2
ML20097D4681991-12-31031 December 1991
Pennsylvania Power & Light Company,1991 Annual Rept
ML18017A0391991-07-26026 July 1991
LER 91-010-00:on 910628,RWCU Isolated on Two Occassions Due to Actuations of Steam Leak Detection Instrumentation. Caused by Design Deficiency & Elevated Ambient Penetration Room Temps.Temp Modules replaced.W/910726 Ltr
1999-09-30
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AC~~ELZRATED DISTRIBUTION DEMONSTRATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:8809290378 DOC.DATE: 88/09/23 NOTARIZED- NO DOCKET FACIL:50-387 Susquehanna Steam Electric Station, Unit 1, Pennsylva 05000387 "
AUTH. NAME AUTHOR AFFILIATION RYDER,T.S. Pennsylvania Power S Light Co.
BYRAM,R.G. Pennsylvania Power 6 Light Co.
RECIP.NAME RECIPIENT AFFILIATION
SUBJECT:
LER 88-018-00:on 880824,one channel of RWCU sys area high temp isolation instrument found inoperable.
W/8 ltr. iI DISTRIBUTION CODE: IE22D COPIES RECEIVED: LTR g ENCL (
TITLE: 50.73 Licensee Event Report (LER), Incident Rpt, etc.
SIZE:
D NOTES:LPDR 2 cys Transcripts. 05000387IB RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL A PD1-2 LA 1 1 PD1-2 PD 1 1 THADANI,M 1 1 INTERNAL: ACRS MICHELSON 1 1 ACRS MOELLER 2 2 ACRS WYLIE 1 1 AEOD/DOA 1 1 AEOD/DSP/NAS 1 1 AEOD/DSP/ROAB 2 2 AEOD/DS P/TPAB 1 1 ARM/DCTS/DAB 1 1 DEDRO 1 1 NRR/DEST/ADS 7E 1 0 NRR/DEST/CEB 8H 1 1 NRR/DEST/ESB 8D 1 1 NRR/DEST/ICSB 7 1 1 NRR/DEST/MEB 9H 1 1 NRR/DEST/MTB 9H 1 1 NRR/DEST/PSB SD 1 1 NRR/DEST/RSB 8E 1 1 NRR/DEST/SGB SD 1 1 NRR/DLPQ/HFB 10 1 1 NRR/DLPQ/QAB 10 1 1 NRR/DOEA/EAB 11 1 1 NRR/DREP/RAB 10 1 1 NRR/DREP/RPB 10 2 2 NRR/DRIS/SIB 9A 1 1 NUDOCS-ABSTRACT 1 1 REG FILE 02 1 1 RES TELFORD,J 1 1 1 1
'RES/DSIR/EIB 1 1 GNl FILE 01 1 1 EXTERNAL EG&G WILLIAMSE S 4 .4 FORD BLDG HOY I A 1 1 R
H ST LOBBY WARD 1 1 LPDR 2 2 NRC PDR 1 1 NSIC HARRIS,J 1 1 I NSIC MAYS,G 1 1 D
NOTES: 2 2 8
A TOTAL NUMBER OF COPIES REQUIRED: LTTR 49 ENCL 48
NRC Form 388 US. NUCLEAR REGULATORY COMMISSION (9-83)
APPROVED OMB NO. 31604104 EXPIRES: 8/31/SS LICENSEE EVENT REPORT (LER)
FACILITYNAME (II DOCKET NUMBER (2I PACE 3 Susquehanna Steam Electric Station Unit 1 0 5 0 0 0 8 7 1 OF0 TITLE (4)
I One Channel of RWCU System Area High Temperature Isolation Instnmant Found Inoperable EVENT DATE (5) LER NUMBER (SI REPORT DATE (7) OTHER FACILITIES INVOLVED (8)
MONTH DAY YEAR YEAR @ StOVENTIAL
'UMBER I 8ES RE~
NUMBER MONTH OAY YEAR FACILITYNAMES DOCKET NUMBER(S) 0 5 0 0 0 0 8 2 4 8 888 0 1 8 00 092 3 88 0 5 0 0 0 THIS REPORT IS SUBMITTED PURSUANT TO THE REOUIREMENTS OF 10 CFA ('I t (Check onr ot mote ol tbr folios(for) (11)
OPERATINO MODE (9) 20A02(b) 20AOS(c) 60.73(sl(2)(lv) 73.71(b)
POWER 20.405(e) (1) (II 5028(c) (1) ~
60.73(e) (2l(v) 73.71(c)
(2)(rill LEVEL 1 p p 20.405(e)(1)(N) 50.38(c) (2) 60.73(e)(2)(ril) OTHER (Specify In Abttrrct below end In Test, HI(C Form P'gA" 20.405(e) 0)(ill) X 60.73(s)(21(II 50.73(e) (2)(vill)(A) 3EBAJ 20AOS(s)(t)(lvl 50.73(e)(2)(ll) 50.73 (sl (8) 20.405(s)(t I(v) 50.73(s) (2) (IB) 60.73(e) (2)(s)
LICENSEE CONTACT FOR THIS LER (12)
NAME TELEPHONE NUMBER AREA CODE T.S. der Pn)er Production En ineer 71 754 2 2 3 5 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)
MANUFAC. AEPORTABLE MANUFAC EPORTABLE CAUSE SYSTEM COMPONENT TO NPADS CAUSE SYSTEM COMPONENT TURER 'URER TO NPRDS o
'w
.w aa v'.t, ..,,....
I<<RM SUPPLEMENTAL REPOAT EXPECTED (14) MONTH DAY YEAR EXPECTED SU 8 M I SS ION DATE (16)
YES (II yrs, complrtr EXPECTED SIIB4(ISSIOH OATEI X NO ABsTRAcT (Limit to lr00 tpecrt, I.e., epptoslmetrly fi(tern tlnrfreprce typewritten llnNI (18)
On August 24, 1988, it was discovered that the HWCU Pump Room ambient temperature sensor, TE-G33-1N016A, was not installed per design. TE-G33-1N016A was discovered to have been installed in a location in which detected a HWCU steam leak in the HNCU Pump Room area. The installation error it would not have was discovered during a walkdown of the steam leak detection system. The walkdawn had been initiated in response to recent problems identified on the MSL DT trip logic. Root cause of this event was attributed to a lack of installation detail on the design documents for the steam leak detection system. The ventilation drawing used for identification of instrument location for TE-G33-1N016A was vague and did not clearly shaw the mounting location.
This resulted in the temperature sensor being installed inside 'the main steam tunnel exhaust duct instead of being installed on the wall of the HWCU pump rocm. The event has been determined to be reportable per 10CFR50.73(a)(2)(i)(B), in that one trip logic channel for the HNCU Pump Room HWCU leak detection ambient temperature trip logic has been inoperable prior to August 24, 1988 and would not have been able to perform its design function. A new temperature instrument was installed in the proper location within the HWCU Pump Room and the original temperature instrument was left as a spare device in the MSL exhaust duct. A task force is in the process of reviewing the entire steam leak detection system for adegcacy and will be providing recammndations for permanent corrective action. The findings of this task team will be reported in a follawup to LER 88-017-00 (Docket 50-387) and this LER will not be updated.
SSO 3 ('S0929037S PDR ADOCK 050 03S7 I PDC NRC Form 3SS (983)
NRC Form 366A U.S. NUCLEAR REOULATORY COMMISSION (943) r LICENSEE EVENT REPORT (LER) TEXT CONTINUATION APPROVEO OMB NO. 3150M(04 EXPIRES: 8/31/68 FACILI'TY NAME (1) OOCKET NUMBER (2) LER NUMBER (6) PACE (3)
%ca EEQUENTIAL iPSI REvlsloN YEAR CON NVMSCR (~" NVMCER Unit 1 Sus ehanna Steam Electric Station 05000387 8 8 018 0 0 0 30F 0 3 TEXT ///more space /s a/O/rarL usa ///Oora/HRC Form365rE's/03)
CORRECZIVE ACZIONS A request for enforcement discretion was subnitted to the NHC for relief fran Technical Specification 3.3.2. The provisions of this technical specification require placing the trip system in the tripped condition or closing the affected system isolation valves either of which would have caused isolation of HhUJ fran the reactor vessel until the inoperable channel of HNCU temperature isolation instrumentation could be restored to operable status. Having HNCU isolated fran the reactor vessel for the extended period of time anticipated to return the inoperable channel to operable status would result in significant degradation of reactor coolant chemistry and could eventually require shutting the unit. dawn. The request was granted for the period of time ending at, 11:00 a.m. on August 29, 1988. On August 26f 1988 a new temperature instr(ment was installed in the proper location within the HNCU Pump Roan and the original temperature instrument was left as a spare device at its location in the main steam tunnel exhaust duct. Appropriate drawings were revised to reflect the new plant configuration for these devices. A task team had been previously formulated to review the subject of steam leak detection. An in-depth review
, will be performed for all leak detection systems including the HNCU, Residual Heat Removal (RHR, EIIS Code: BO), Reactor Core Isolation Cooling (RCIC, EIIS Code: BN), High Pressure Coolant Injection (HPCI, EIIS Code: BJ), and MSL Leak Detection Systems. Calculations and design bases will be reviewed for adequacy and determination of the root cause and appropriate long-term corrective actions will be performed. The findings of this task team will be reported in a followup to LER 88-017-00 (Docket 50-387) and this LER will not be updated.
ADDITIONAL INFORMATION Failed Caagmnent Identification: Not applicable.
Previous Similar Events: Not Applicable NRC fORM 366A *U.S.GPO:(985&524 538/455 (983)
NRC Form'3SBA U.S, NUCLEAR REGULATORY COMMISSION (543)
LICENSEE EVENT REPORT (LER) TEXT CONTINUATION APPROVED OMS NO. 3)50-GIGA EXPIRES: 5/3)/SS FACILITYNAME l)l DOCKET NUMBER (2) LER NUMBER (5) PAGE (3)
"EAR ')k SEOVENTIAL NUMBER REVISION NUMBER Unit 1 Susquehanna Steam Electric Station o 5 o o o 3 8 7 8 8 0 0 2 OF 0 3 TEXT //fmoro F/>>co /F /Fr/ro ~ / Iroo ////Or>>/ HRC Forrrr 35EA'F/ 07)
DESCRIPTION OF EVEÃZ On August 24, 1988, EIIS Code: CE) Pump Roam it was ambient discovered that the Reactor Water Cleanup temperature sensor, TE-G33-1N016A, (HWCU, was not installed per design. TE-G33-1N016A had been installed in a location in which it would not have detected a steam leak in the HWCU Pump Roam area. The installation error was discovered during a walkdown of the steam leak detection system. The walkdown had been initiated in response to recent problems identified on the Main Steam Line (MSL, EIIS Code: SB) differential temperature trip logic which were reported in LER 88-016-00 (Docket 50-387) .
CAUSE OF EVENT Root cause of this event was attributed to a lack of installation detail on the design documents for the steam leak detection system. The ventilation drawing (V-28-5) used for identification of instrument location for TE-G33-1N016A was vague and did not clearly show the mounting location. This resulted in the te(T)perature sensor being installed inside the main steam tunnel exhaust duct instead of being installed on the wall of the RÃCU pump roan.
REPORTABILITY/ANALYSIS The event had been deteznuned to be reportable per 10CFR50.73(a) (2) (i) (B), in that one trip logic channel for the HNCU Pump Room HNCU leak detection ambient te(nperature trip logic has been inoperable prior to August 24, 1988 and would not have been able to perform its design function. Section 7.3.1a.2.4.1.9, 6
.10 of the FSAR provide discussion on the various methods of leak detection available to detect a steam leak associated with the HWCU system. "Diversity of trip initiation signals for RWCU system line break is provided by high differential flow, high flow, ambient and differential temperature, and Reactor Vessel low, low water level, Level 2. An increase in differential flow, space taT)perature, differential temperature, or low Reactor Vessel water level will initiate HWCU isolation." With exception of this channel and the penetration room DT detection, inoperable prior to August 5, 1988 as reported in LER 88-017-00 (Docket 50-'387), the remaining safety systems were in tact to detect a breech in the reactor coolant pressure boundary for the HNCU,system. There was no caT)pranise to the health and safety of the public and no safety consequences occurred.
NRC FORM SBBA o U.S.GPO: I SSS O 52E 535/EES (543)
Pennsylvania Power & Light Company Two North Ninth Street ~ Allentown, PA 18101 ~ 21517705151 September 23, l988 U.S. Nuclear Regulatory Carmission Docum nt Control Desk Washington, DC 20555 t[
SUSQUKRNNA STEM EKZCTRIC STATION LICENSEE EVENT REPORT 88-018-00 FILE R41-2 PLAS - 338 Docket No. 50-387 License No. NPF-14 Attached is Licensee Event Report 88-018-00. This event was determined reportable per 10CFR50.73(a) (2) (i) (B) in that one channel of the Reactor Water Cleanup System Area High Temperature isolation instrumentation was- found to be inoperable due to mislocation of a temperature sensor.
R.G.
Superin ent of Plant Susquehanna TSR/mjm cc: Mr. William T. Russell Regional Administrator, Region I U.S. Nuclear Regulatory Ccmtission 475 Allendale Road King of Prussia, PA 19406 Mr. Frank Young Sr. Resident Inspector U.S. Nuclear Regulatory Ccmtission P.O. Box 52 Shickshinny, PA 18655
